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Despite interesting properties, the use of 67Cu, 186Re and 47Sc theranostic radionuclides in preclinical studies and clinical trials is curtailed by their limited availability due to a lack of widely established production methods. An IAEA Coordinated Research Project (CRP) was initiated to identify important technical issues related to the production and quality control of these emerging radionuclides and related radiopharmaceuticals, based on the request from IAEA Member States. The international team worked on targetry, separation, quality control and radiopharmaceutical aspects of the radionuclides obtained from research reactors and cyclotrons leading to preparation of a standard recommendations for all Member States. The CRP was initiated in 2016 with fourteen participants from thirteen Member States from four continents. Extraordinary results on the production, quality control and preclinical evaluation of selected radionuclides were reported in this project that was finalized in 2020. The outcomes, outputs and results of this project achieved by participating Member States are described in this minireview.

Cross sections of alpha-particle induced reactions were determined on antimony targets using alpha-particle irradiation with a primary energy of 50 MeV. The standard stacked target technique, activation method and offline gamma-ray spectrometry were applied for determination of the reaction cross sections. Thin Sb targets prepared by vacuum evaporation onto Kapton backings were activated. Ti foils were inserted into the stack for monitoring the alpha-particle beam parameters and energy loss of the particles in the target by using the natTi(α,x)51Cr monitor reaction. Reaction cross sections for formation of 121,123,124,125,126I, 121m,g,123m,125mTe and 118m,120m,122gSb were determined and compared to the available literature data and theoretical estimation of the cross sections from the TENDL-2019 data library.

The 67Cu is considered as one of the most perspective radio isotopes in targeted radio-immunotherapy medical applications. 67Cu is a β–-emitter with a mean β– energy, which allows treating tumors in size up to about 4 mm. Its decay is followed by emission of low energy gamma-rays suitable for gamma-camera imaging. The about three days half-life (T1/2 = 61.83 h) is optimal for human applications. However, one of the main drawback factors for its application is still the limited supply of 67Cu. There are several possibilities to produce 67Cu. High flux reactors, charged particle accelerators and high-energy bremsstrahlung radiations can be used to produce 67Cu. In this work we have studied one of the promising charged particle production routes based on the 64Ni(α,p)67Cu nuclear reaction. Cross sections for formation of 67,64,61,60Cu, 62,63Zn and 56,57Ni were studied up to 50 MeV alpha-particle energy on nickel targets with natural isotopic composition.

Activation cross sections of the 169Tm(p,n)169Yb reaction were measured up to 18 MeV. The stacked-foil activation technique and the high-resolution gamma-ray spectrometry were adopted to derive the cross sections. The result is compared with previous experimental data and theoretical model calculation. Physical yield of 169Yb is derived from the measured cross sections and compared with those from other production routes.

In a systematic study of light charged particle induced nuclear reactions we investigated the excitation functions of deuteron induced nuclear reactions on natural lutetium targets. Experimental excitation functions up to 50 MeV on high purity natLu were determined using the standard stacked foil activation technique. High resolution off-line gamma-ray spectrometry was applied to assess the activity of each foil. From the measured activity direct and/or cumulative elemental cross-section data for production of 171,172,173,175Hf, 171,172,173,174g,176m,177m,177gLu and 169Yb radioisotopes were determined. The experimental data were compared to results of the TALYS theoretical code taken from the TENDL databases and results of our calculations using the ALICE-IPPE-D and the EMPIRE-D codes. No earlier experimental data were found in the literature. Thick target yields for the investigated radionuclides were calculated from the measured excitation functions.

Deuteron induced reactions on natural bismuth targets were investigated with the stacked foil activation technique up to 50 MeV. Excitation functions for the reactions $$^{\mathrm {209}}$$ 209 Bi(d,xn)$$^{\mathrm {207,206,205}}$$ 207 , 206 , 205 Po, Bi(d,x)$$^{\mathrm {207,205}}$$ 207 , 205 Bi and $$^{\mathrm {209}}$$ 209 Bi(d,x)$$^{\mathrm {203}}$$ 203 Pb obtained from gamma-spectra of decay products were compared with the results of our ALICE-D and EMPIRE-D model calculations, with the result of TALYS code taken from TENDL-2019 on-line library and the results of the only measurement performed earlier. Thick target yields were deduced from the fitted experimental cross sections.

An experiment of α -induced reactions on yttrium-89 was performed to investigate the excitation functions of 89 Zr and 90 Nb , which are suitable for immuno-PET studies. The stacked-foil method, activation technique, and off-line γ -ray spectrometry were used for this investigation. The excitation functions of 92 m , 91 m , 89 m , 89 g Nb , 88 Zr , and 90 m , 88 g , 87 m , 87 g Y were also derived and compared with earlier experimental and the TENDL-2017 data. Good agreements with part of the previous studies were found.

As an alternative production route for the medically interesting 178mTa isotope production cross sections of alpha particle induced nuclear reaction of the natHf(α,x)178W–178mTa process was investigated. Activation method, stacked target technique, and high resolution off-line γ-ray spectrometry were applied. Excitation functions of the natHf(α,x)178W reaction and of several other side reactions were determined up to 51 MeV. Activation cross section data were determined for the following reactions: natHf(α,x)176,177,178W, natHf(α,x)175,176,177,178g,180g,182g,183Ta, and natHf(α,x)173,175,179m2,180m,181Hf. The measured experimental data were compared with the results of earlier experimental data and the results of TALYS nuclear reaction model code calculation tabulated in the TENDL-2017 data library. Experimental data are presented for the first time in the 40–50 MeV energy region. Thick target yields were calculated for elemental hafnium target using the fitted experimental cross section data.

Activation cross sections of α-particle induced reactions on natYb were measured. The stacked foil technique, the activation method and the γ-ray spectrometry were used. The stacked target consisted of natYb and natTi foils was irradiated with a 51.0-MeV α beam at the RIKEN AVF cyclotron. The γ rays emitted from the irradiated foils were measured using a high-resolution HPGe detector. Production cross sections of 170,171,172,173,175Hf, 171,172,173,177gLu and 169Yb were determined. The results were compared with previous experimental studies and theoretical calculations. For most of the reactions a consistent agreement was found.

The activation cross sections of the alpha-particle induced reactions on natural palladium were determined up to 50 MeV using the stacked-foil technique and high-resolution gamma-ray spectrometry. Production cross sections of 111m,109,107,105,104Cd and 111g,110m,106m,105g,103gAg were obtained. The results were compared with the data of previous experiments and results of theoretical model calculations.

This work presents the recoil and secondary implantation of radioisotopes at different bombarding energies in the range of ~ 13 to ~ 40 MeV by using an α-particle beam of 50 MeV irradiating a stack of Ag, Ni and Ti metal foils. Activation cross-sections for the produce radioisotopes were calculated and confronted with literature data. The implanted activity is presented as a function of the primary beam energy for six produced radioisotopes 57Ni, 57Co, 65Zn, 51Cr, 48V and 46Sc. The use of each of these radioisotopes in engineering experiments based on the nano-thin layer activation is discussed.

In the frame of a systematic study of activation cross sections of deuteron induced reactions, experimental cross section data were measured on Mn (monoisotopic Mn-55) up to 50MeV for the formation of Mn-56,Mn-54,Mn-52, V-48 and Cr-51 by using stacked-foil activation method and high resolution gamma spectrometry. The experimental data are compared with the earlier published data and with the results predicted by the ALICE-IPPE-D and EMPIRE-II-D theoretical codes, and with the data taken from the on-line TENDL-2017 library.

Cross sections of α-induced reactions on natural zirconium were measured up to 50 MeV using the stacked-foil technique, activation method and high resolution γ-ray spectrometry. The production cross sections of 93m,99Mo, 90g,92m,95g,95m,96Nb and 88,89g,95Zr were determined and compared with other experimental data measured earlier and result of theoretical calculations. The integral thick target yield of 99Mo was deduced from the measured cross section data.

Natural silver targets have been irradiated by using a 50 MeV alpha-particle beam in order to measure the activation cross sections of radioisotopes in the 40–50 MeV energy range. Among the radio-products there are medically important isotopes such as 110mIn and 111In. For optimizing the production of these radioisotopes and regarding their purity and specific activity the cross section data for every produced radioisotope are important. New data are measured in this energy range and the results of some previous measurements have been confirmed. Physical yield curves have been calculated by using the new cross section data completed with the results from the literature.

In the frame of a systematic study of deuteron induced nuclear reactions on all elements, activation cross sections on $$^{\mathrm {nat}}$$ nat Se were investigated. Excitation functions were measured up to 50 MeV particle energy for production of $$^{\mathrm {82}}$$ 82 Br(m$$+)$$ + ) ,$$^{\mathrm {80m}}$$ 80 m Br, $$^{\mathrm {77}}$$ 77 Br(m$$+)$$ + ) ,$$^{\mathrm {76}}$$ 76 Br(m$$+)$$ + ) , $$^{\mathrm {75}}$$ 75 Br, $$^{\mathrm {75}}$$ 75 Se(cum), $$^{\mathrm {73}}$$ 73 Se(cum), $$^{\mathrm {76}}$$ 76 As,$$^{\mathrm {74}}$$ 74 As, $$^{\mathrm {73}}$$ 73 As(cum), $$^{\mathrm {72}}$$ 72 As and $$^{\mathrm {71}}$$ 71 As(cum) by using the activation method through stacked foil irradiation followed by off-line gamma-ray spectrometry. The experimental results were compared to the earlier experimental data and to excitation functions calculated with the ALICE-D and EMPIRE-D theoretical model codes and data given in the TENDL-2019 on-line library based on TALYS calculations.

Excitation functions of alpha-particle induced reactions on natNd up to 50 MeV were measured at the RIKEN AVF cyclotron. To derive cross sections activation method, stacked target technique and gamma-ray spectrometry were adopted. Formations of 153,145Sm, 151,150,149,148m,148g,144,143Pm, and 149,147Nd were investigated. The results were compared with the previous experimental data and the TENDL-2019 data. Discrepancies among most of them were found.

Activation cross sections of the $$^{\mathrm {nat}}\hbox {Rb (d,xn)}^{87\mathrm {m,85m,85g,83,82}}\hbox {Sr}$$ nat Rb (d,xn) 87 m , 85 m , 85 g , 83 , 82 Sr , $$^{\mathrm {nat}}\hbox {Rb(d,x)}^{\mathrm {86,84,83,82m}}\hbox {Rb}$$ nat Rb(d,x) 86 , 84 , 83 , 82 m Rb and $$^{\mathrm {nat}}\hbox {Rb(d,x)}^{85\mathrm {m}}\hbox {Kr}$$ nat Rb(d,x) 85 m Kr nuclear reactions have been measured for the first time through an activation method combining the stacked foil irradiation technique and gamma-ray spectrometry. The provided cross sections from the present investigation are all new, in such a way contribute to the completeness of the experimental database. The experimental cross sections were compared with the theoretical prediction in the TENDL-2019 TALYS based library and with our calculation using ALICE-D and EMPIRE-D model codes in order the improve their predictivity. Thick target production yields were calculated form the new cross sections for all investigated radioisotopes. Practical applications of the results are shortly discussed.

Additional excitation functions for deuteron induced reactions up to 48.6 MeV on quasi mono-isotopic Ta (99.99% Ta-181) were experimentally determined using the activation method through stacked foil irradiation. Cross-sections for the production of W-17(7,)17(8,)181, Ta-177cum(, )178g,180g(, )182m+g and Hf-175,179m2,18(0m,)181 were derived from high resolution gamma-spectrometry and X-ray analysis. Comparison with the few earlier published experimental data and with values predicted by the theoretical code TALYS 1.6 (as available in the on-line library TENDL-2019) are discussed. Thick target yields for medically or industrially relevant longer-lived Ta-177,178g(,1)80g,182m+g and W-178(,1)81, calculated from fits to our experimental excitation curves, are discussed. Estimations on possible occupational doses to maintenance or scientific personnel around high power accelerators originating from activated Ta structural elements are updated.

Despite interesting properties, the use of

New experimental cross sections in the 13–21.5 MeV domain of deuteron induced reactions on Te complementing the 35-year-old publication by Zaidi et al. [1] were determined. Excitation functions for the 121,123,124,125,126,128,130,131I-radioisotopes and 131gTe were obtained through stacked foil activation method. Values for 128,121I and 131Te are the first ever presented for natTe. A comparison of our new cross-section values is made to the values reported in the earlier study where relevant and with the theoretical excitation functions reconstructed from the reaction cross sections available in the TENDL-2017 (TALYS 1.6 calculations) on-line library. For discussion of the possibility as a production route the yields of 123,124,125,126,131I are calculated from fits to our measurements, complemented by theoretical values. Contributing reactions and contaminations in selected energy windows are discussed and compared to earlier conclusions.

The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by the IAEA Nuclear Data Section (NDS) is successfully collaborating in the maintenance and development of the EXFOR library. As the scope of published data expands (e.g., to higher energy, to heavier projectile) to meet the needs from the frontier of sciences and applications, it becomes nowadays a hard and challenging task to maintain both completeness and accuracy of the whole EXFOR library. The paper describes evolution of the library with highlights on recent developments., 4 pages, 2 figures

The EXFOR library has served as the unique repository of experimental cross section and other nuclear reaction data for 50 years. The Nuclear Reaction Data Centres (NRDC) have compiled data sets from more than 22000 experimental works for the EXFOR library. Our collaboration and effort on improvement of EXFOR coverage are described in this paper, as well as tools for digitization of numerical data from graph images developed by us for EXFOR compilation.

Activation cross sections of application related Cd-107 and Cd-109 via proton, deuteron, alpha particle induced reactions on palladium, He-3 and alpha particle induced nuclear reactions on silver and deuteron induced reactions on cadmium and indium were measured by using the stacked foil irradiation technique and gamma-ray spectrometry. The cross sections were compared with the earlier experimental data and theoretical predictions. Integral yields were deduced on the basis of experimental data. Different production routes for both radioisotopes are compared.

Purpose This paper aims to investigate the wear behaviour of different materials for cylinder liners and piston rings in a linear reciprocating tribometer with special focus on the wear of the cylinder liner in the boundary lubrication regime. Design/methodology/approach Conventional nitrided steel, as well as diamond-like carbon and chromium nitride-coated piston rings, were tested against cast iron, AlSi and Fe-coated AlSi cylinder liners. The experiments were carried out with samples produced from original engine parts to have the original surface topography available. Radioactive tracer isotopes were used to measure cylinder liner wear continuously, enabling separation of running-in and steady-state wear. Findings A ranking of the material pairings with respect to wear behaviour of the cylinder liner was found. Post-test inspection of the cylinder samples by scanning electron microscopy (SEM) revealed differences in the wear mechanisms for the different material combinations. The results show that the running-in and steady-state wear of the liners can be reduced by choosing the appropriate material for the piston ring. Originality/value The use of original engine parts in a closely controlled tribometer environment under realistic loading conditions, in conjunction with continuous and highly sensitive wear measurement methods and a detailed SEM analysis of the wear mechanisms, forms an intermediate step between engine testing and laboratory environment testing.

The cross sections of the proton, deuteron and α-particle induced nuclear reactions on Ca were determined experimentally up to 20 MeV. The obtained experimental data were validated theoretically using EMPIRE-3.2 and TALYS-1.6. The production yields of 43Sc and 44m,gSc radioisotopes were calculated and discussed in view of the reported experimental data. Of all the production routes, the 44Ca(p,n)44m,gSc and 43Ca(d,n)44m,gSc showed highest yields of 1206 MBq/µA.h (15 → 5 MeV) and 204 MBq/µA.h (8 → 0 MeV), respectively. The α-particles induced reactions on natCa or 40Ca were found to be suitable for producing considerable activity of 43Sc at energy range 8–20 MeV.

In the frame of a systematic study of deuteron induced activation processes on middle mass elements, excitation functions of the Ba-nat(d,X) La-135,La-133,La-132, Ba-135m,Ba-133m,Ba-133mg,Ba-131mg Cs-136mg,Cs-134mg,Cs-132,Cs-129 reactions were measured up to 50 MeV for the first time. Cross sections were measured with the activation method using a stacked foil irradiation technique followed by HPGe gamma-ray spectrometry. A comparison with the results of the nuclear model TALYS code (reported in the TENDL-2015 library) was done. The potential use of the deuteron induced reactions on Ba for applications (Cs-131 and Ba-131 production) is discussed.

In the framework of a systematic study of proton induced nuclear reactions on lanthanides we have measured the excitation functions on natural cerium for the production of (142,139,138m,137)pr, Ce-141.139,Ce-137m,Ce-137g,Ce-135 and La-133 up to 65 MeV proton energy using the activation method with stacked foil irradiation technique and high-resolution gamma-ray spectrometry. The cross-sections of the investigated reactions were compared with the data retrieved from the TENDL-2014 and TENDL-2015 libraries, based on the latest version of the TALYS code system. No earlier experimental data were found in the literature. The measured cross-section data are important for further improvement of nuclear reaction models and for practical applications in nuclear medicine, other labeling and activation studies. (C) 2017 Elsevier B.V. All rights reserved.

In the frame of a systematic study of the activation cross sections of charged particle induced nuclear reactions on rare earths for production of therapeutic radionuclides, proton induced reactions on neodymium were measured up to 65 MeV energy, above 45 MeV for the first time. The excitation functions of the Nd-nat(p,x)Pm-150,Pm-149,Pm-148m,Pm-148g,Pm-146,Pm-144,Pm-143,Pm-141, Nd-149,Nd-147,Nd-141,Nd-140,Nd-139m,Nd-138, Pr-142,Pr-138m and Ce-139g nuclear reactions were assessed by using stacked foil activation technique and high resolution gamma-spectrometry. The excitation functions were compared to the theoretical predictions, available in the TENDL-2015 library based on latest version of the TALYS code. The application of the data for medical isotope production is shortly discussed.

The excitation functions of deuteron-induced reactions on 169Tm were measured using the stacked-foil method and high resolution gamma-ray spectrometry. The production cross sections of a medical radionuclide 169Yb were investigated. The result was compared with the previous experiments and found to be in good agreement. In addition to 169Yb, the production cross sections of Tm isotopes, 170Tm, 168Tm and 167Tm, were measured. These results were compared with the TALYS calculations taken from the TENDL-2015 online data library.

In the frame of a systematical study of light ion induced nuclear reactions on platinum, activation cross sections for deuteron induced reactions were investigated. Excitation functions were measured in the 20.8–49.2 MeV energy range for the natPt(d,xn) 191,192,193,194,195,196m2,196g,198g,199Au, natPt(d,x) 188,189,191,195m,197m,197gPt and natPt(d,x) 189,190,192,194m2Ir reactions by using the stacked foil irradiation technique. The experimental results are compared with previous results from the literature and with the theoretical predictions in the TENDL-2014 and TENDL-2015 libraries. The applicability of the produced radio-tracers for wear measurements has been presented.

The main goals of this investigations were to expand and consolidate reliable activation cross-section data for the nat Mo(α,x) reactions in connection with production of medically relevant 97,103 Ru and the use of the nat Mo(α,x) 97 Ru reaction for monitoring beam parameters. The excitation functions for formation of the gamma-emitting radionuclides 94 Ru, 95 Ru, 97 Ru, 103 Ru, 93m Tc, 93g Tc(m+), 94m Tc, 94g Tc, 95m Tc, 95g Tc, 96g Tc(m+), 99m Tc, 93m Mo, 99 Mo(cum), 90 Nb(m+) and 88 Zr were measured up to 40 MeV alpha-particle energy by using the stacked foil technique and activation method. Data of our earlier similar experiments were re-evaluated and resulted in corrections on the reported results. Our experimental data were compared with critically analyzed literature data and with the results of model calculations, obtained by using the ALICE-IPPE, EMPIRE 3.1 (Rivoli) and TALYS codes (TENDL-2011 and TENDL-2015 on-line libraries). Nuclear data for different production routes of 97 Ru and 103 Ru are compiled and reviewed.

Activation cross sections of the La-nat(p,x)Ce-139,Ce-137m,Ce-137g,Ce-135,Ce-134,Ce-133m, La-nat(p,x)La-135,La-134,La-133 and Ba-133m,Ba-133g,Ba-131 nuclear reactions have been measured experimentally, for the first time (except Ce-139). Cross-sections in the 34-64 MeV energy range were obtained through an activation method combining the stacked foil irradiation technique and gamma-ray spectrometry. The experimental cross sections were compared with the theoretical prediction in the TENDL-2014 and TENDL-2015, TALYS based libraries. Applications in the field of medical radionuclides production is discussed.

New experimental excitation functions for proton induced reactions on W-nat are presented in the 32-65 MeV energy range. The cross-sections for W-nat(p,xn)Re-186,Re-184m,Re-184g,Re-183,Re- 182m,Re-182g,Re-181 W-nat(p,x)W-178, W-nat(p,x)Ta-183,Ta-182,Ta- 180m,Ta- 177,Ta-176,Ta-175, Hf-175 and Lu-177 were measured via an activation method by using a stacked-foil irradiation technique and high resolution gamma-ray spectroscopy. The results were compared with predicted values obtained with the nuclear reaction code TALYS (results taken from the TENDL 2014 and TENDL 2015 on-line libraries). Production routes of the medically relevant radionuclides Re-186, the W-178 -> Ta-178 generator and W-181 are discussed. (C) 2016 Published by Elsevier B.V.

Using the stacked-foil activation technique, cross-sections of deuteron induced reactions on natural Sn targets were determined up to 50 MeV. Excitation functions are reported for the product nuclides 116mSb, 117Sb, 118mSb, 120mSb 122m+gSb, 124m+gSb, 110Sn(cum), 113m+gSn(cum), 117mSn, 110mIn(cum), 110gIn, 111m+gIn(cum), 113mIn, 114mIn 115mIn. Comparison with earlier published data at lower energy is discussed. For all excitation functions a theoretical calculation using the TALYS 1.6 (on-line TENDL-2015 library) code is shown.

In the frame of a thorough investigation of activation cross sections of deuteron induced nuclear reactions, excitation functions on iridium were investigated up to 50 MeV deuteron energy. Production cross sections were measured for the Pt-193m, Pt-191, Pt-189, Pt-188, Pt-187, Ir-194m2, Ir-194g(m1 +), Ir-192g(m1 + ), Ir-190m, Ir-190g (m1 + ), Ir-189, Ir-188, Ir-187 and (191g) Os(m1 + ) radionuclides. Activation method, stacked foil irradiation technique and offline gamma-ray spectrometry were used for quantification of the radionuclides. The experimental results are compared with earlier data in the overlapping energy range. We discuss theoretical predictions obtained from the ALICE-IPPE-D and EMPIRE-II-D codes. The experimental data are also compared with calculated values reported in the TENDL-2017 on-line library calculated by using the TALYS code.

Additional experimental activation cross sections for deuteron induced reactions on platinum were measured in the 35-49MeV energy range for the Pt-nat(d,xn)Au-191,Au-192,Au-193,Au-194,Au-195,Au-196m2,Au-196g,Au-198m,Au-198g,Au-199, Pt-nat(d,x)Pt-189,Pt-191,Pt-193m,Pt-195m,Pt-197g and Pt-nat(d,x)Ir-188,Ir-189,Ir-190m2,Ir-190,Ir-192,Ir-194m2 reactions by using the stacked foil irradiation technique and gamma ray spectrometry. The available experimental results are compared with the calculated values based on ALICE-D and EMPIRE-D model codes and with the theoretical predictions in the TALYS based TENDL-2017 library.

An IAEA coordinated research project that began in 2012 and ended in 2016 was primarily dedicated to the compilation, evaluation and recommendation of cross-section data for the production of medical radionuclides. One significant part of this work focused on diagnostic positron emitters. These particular studies consist of 69 reactions for direct and indirect or generator production of 44Sc(44Ti), 52mMn(52Fe), 52gMn, 55Co, 61Cu, 62Cu(62Zn), 66Ga, 68Ga(68Ge), 72As(72Se), 73Se, 76Br, 82Rb(82Sr), 82mRb, 86Y, 89Zr, 90Nb, 94mTc, 110mIn(110Sn), 118Sb(118Te), 120I, 122I(122Xe), 128Cs(128Ba), and 140Pr(140Nd) medical radionuclides. The resulting reference cross-section data were obtained from Pade fits to selected and corrected experimental data, and integral thick target yields were subsequently deduced. Uncertainties in the fitted results were estimated via a Pade least-squares method with the addition of a 4% assessed systematic uncertainty. Experimental data were also compared with theoretical predictions available from the TENDL-2015 and TENDL-2017 libraries. All of the numerical reference cross-section data with their corresponding uncertainties and deduced integral thick target yields are available on-line at the IAEA-NDS medical portal www-nds.iaea.org/medicalportal and also at the IAEA-NDS web page www-nds.iaea.org/medical/positron_emitters.html .

As a part of our systematical study of activation cross sections of deuteron induced nuclear reactions, cross sections on hafnium were investigated up to 50 MeV. Excitation functions were measured for the nat Hf(d,xn) 178g,177,176,175,173 Ta, nat Hf(d,x) 181,180m,179m2,175,173,172 Hf, nat Hf(d,x) 173,172,171,170 Lu and nat Hf(d,x) 169 Yb reactions by using the activation method, stacked foil irradiation technique and off-line gamma-ray spectrometry for quantification of the produced radionuclides. The experimental results are compared with the earlier results in the overlapping energy range, and with the theoretical predictions of the ALICE IPPE-D and EMPIRE II-D theoretical codes and with values reported in the TENDL-2017 on-line library obtained with the TALYS code.

International audience; Increasing interest in the treatment of human disease by means of targeted radionuclide-based therapies requires an accurate understanding of achievable yields and quantification of realisable degrees of purity. Important studies within a more extensive Coordinated Research Project of the International Atomic Energy Agency (IAEA CRP) have included in-depth assessments and evaluations of all available measured cross-section data for ten nuclear reactions leading to the formation of $^{131}$Cs, $^{131}$Ba, $^{225}$Ac, $^{225}$Ra, $^{227}$Th, $^{227}$Ac, $^{230}$U and $^{230}$Pa for various on-going and proposed therapeutic applications in nuclear medicine. Equivalent studies were also undertaken of possible reactions to produce the $^{178}$W/low-spin $^{178m}$Ta generator system that has been clinically applied in diagnosis by means of SPECT - these particular cross-section studies and recommendations are included in this paper for completeness. All available measured data have been critically reviewed and assessed to produce statistically consistent datasets. Selected datasets have been fitted by a least-squares method with Padé approximations of variable order to evaluate the production cross sections and corresponding uncertainties. New measurements have been made in some instances, and reported data have been adjusted to accommodate new nuclear decay or monitor reaction data which altered the original reported quantities adversely. Insufficient measured data are available in many cases to permit a reliable evaluation of cross sections, and these instances are discussed. Recommended therapeutic radionuclide production reaction data and their uncertainties are available on the Web page of the IAEA Nuclear Data Section at www-nds.iaea.org/radionuclides/ and also at the IAEA medical portal www-ds.iaea.org/medportal/

The excitation functions of 89Y( $\alpha$ ,n) 92mNb, 89Y(d, $\alpha$ )87mSr, 89Y(d,2n)89cumZr and 89Y(d,p)90mY nuclear reactions using 10 MeV deuterons and 20 MeV $\alpha$ -particles were measured. Thin samples of Y2O3 were prepared on Al substrates using the sedimentation method. Two different stacks were irradiated for each nuclear reaction to cover all the energy range from threshold to maximum energy of the incident particle. Model calculations of the excitation functions of the above-mentioned nuclear reactions were performed using TALYS-1.6 and EMPIRE-3.2 codes. Variation of the input parameters on the TALYS code results were investigated by using different optical model parameters (OMP). The integral thick target yields were estimated for the investigated reactions based on the proposed average excitation functions.

Activation cross sections of the medically interesting radionuclide 45Ti were investigated in the deuteron-induced reaction on 45Sc. 45Ti can be produced in a radioactive-contamination-free form in the 45Sc(d,2n)45Ti reaction below 15 MeV deuteron energy. The stacked foil activation technique and γ-ray spectrometry were used to determine the cross sections. The physical yield of 45Ti was deduced from the measured cross sections.

The activation cross sections of deuteron induced reactions on natural ruthenium have been measured up to 50 MeV for production of radioisotopes of rhodium (105Rh, 102mRh,102gRh,101mRh,101gRh, 100gRh, 99mRh, 99gRh), ruthenium (105Ru,103Ru (cum), 102Ru (cum), 97Ru (cum), 95Ru (cum)) and of technetium (99mTc, 96gTc (m+), 95mTc (cum), 95gTc (cum), 94gTc,93gTc (m+)). The results are compared with the predictions of the most common theoretical nuclear reaction model codes (ALICE-D, EMPIRE-D and TALYS (TENDL)). From the measured cross section physical yields have been calculated for all measured radioisotopes. The medically important radioisotopes are discussed from the point of view of production routes by charged particle methods and other alternatives.

$^{117m}$Sn is one of the radioisotopes can be beneficially produced through alpha particle irradiation. The targets were prepared by deposition of $^{116}$Cd metal onto high purity 12 $\mu$m thick Cu backing. The average deposited thickness was 21.9 $\mu$m. The beam energy was thoroughly measured by Time of Flight (TOF) methods and proved to be 51.2 MeV. For the experiment the well-established stacked foil technique was used. In addition to the Cd targets, Ti foils were also inserted into the stacks for energy and intensity monitoring. The Cu backings were also used for monitoring and as recoil catcher of the reaction products from the cadmium layer. The activities of the irradiated foils were measured with HPGe detector for gamma-ray spectrometry and cross section values were determined. As a result excitation functions for the formation of $^{117m}$Sn, $^{117m,g}$In, $^{116m}$In, $^{115m}$In and $^{115m,g}$Cd from enriched $^{116}$Cd were deduced and compared with the available literature data and with the results of the nuclear reaction model code calculations EMPIRE 3.2 and TALYS 1.8. Yield curves were also deduced for the measured nuclear reactions and compared with the literature.

The cross sections of alpha particles induced nuclear reactions on natural germanium were investigated by using the standard stacked foil target technique, the activation method and high resolution gamma spectrometry. Targets with thickness of about 1 mu m were prepared from natural Ge by vacuum evaporation onto 25 mu m thick polyimide (Kapton) backing foils. Stacks were composed of Kapton-Ge-Ge-Kapton sandwich target foils and additional titanium monitor foils with nominal thickness of 11 mu m to monitor the beam parameters using the Ti-nat(alpha,x)Cr-51 reaction. The irradiations were done with E-alpha = 20.7 and E-alpha = 51.25 MeV, I-alpha = 50 nA alpha particle beams for about 1 h. Direct or cumulative activation cross sections were determined for production of the Se-72,Se-73,Se-75, (71,72,74,76,78)AS and Ge-69 radionuclides: The obtained experimental cross sections were compared to the results of theoretical calculations taken from the TENDL data library based on the TALYS computer code. A comparison was made with available experimental data measured earlier. Thick target yields were deduced from the experimental cross sections and compared with the data published before.

Cross-sections for formation of activation products induced by protons on natural mercury targets were measured. Results for (196m,196g197g)(cum), (198m),(198g,199g)(cum), (200g)(cum), 201,(202Tl), (194s)(cum), (195g)(cum), (196g)(curn), (198m,199g)(cum) Au and Hg-195m,Hg-197m,Hg-203 are presented up to 65 MeV incident particle energy, many of these for the first time. The experimental data are compared with literature values and with the predictions of the TALYS 1.6 code (results taken from TENDL-2015 on-line library), thick target yields were derived and possible applications in biomedical sciences are discussed. (C) 2016 Elsevier B.V. All rights reserved.

As nuclear medicine community has shown an increasing interest in accelerator produced 99m Tc radionuclide, the possible alternative direct production routes for producing 99m Tc were investigated intensively. One of these accelerator production routes is based on the 100 Mo(p,2n) 99m Tc reaction. The cross section of this nuclear reaction was studied by several laboratories earlier but the available data-sets are not in good agreement. For large scale accelerator production of 99m Tc based on the 100 Mo(p,2n) 99m Tc reaction, a well-defined excitation function is required to optimise the production process effectively. One of our recent publications pointed out that most of the available experimental excitation functions for the 100 Mo(p,2n) 99m Tc reaction have the same general shape while their amplitudes are different. To confirm the proper amplitude of the excitation function, results of three independent experiments were presented (Takacs et al., 2015). In this work we present results of a thick target count rate measurement of the E γ = 140.5 keV gamma-line from molybdenum irradiated by E p = 17.9 MeV proton beam, as an integral benchmark experiment, to prove the cross section data reported for the 100 Mo(p,2n) 99m Tc and 100 Mo(p,pn) 99 Mo reactions in Takacs et al. (2015).